ML20198L123
| ML20198L123 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 12/02/1997 |
| From: | Kenyon T NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9801150176 | |
| Download: ML20198L123 (4) | |
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. December 2. 1997 Mr. Nicholas J. Liparulo, Manager i
Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division Westinghouse Electric Corporation i
P.O. Box 355
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Pittsburgh, PA 15230 i
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO CONTROL ROOM i
HABITABILITY ON THE 1P600
Dear Mr. Liparulo:
As a rasalt of its review of the June 1992 application for design certification of the AP600, the l
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staff has prepared the final safety evaluation report (FSER) on Section 6.4 of the AP600
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Standard Safety Analysis Report (SSAR). The FSER identifies an open item needing resolution
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by Westinghouse befo.., the staff can complete its review of this SSAR section. The open item is identified in the enclosure as Q470.46F.
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You have requested that portions of the information submitted in the June 1992 application for m
s design certification be exempt from mandatory public disclosure. While the staff has not
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- completed its review ot your request in accordance with the requirements of 10 CFR 2.790, that ( '
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, portion of the submitted infomistion is being withheld from public disclosure pending the staffs 4 w!
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- final detennination. The staff concludes that the enclosure does not contain those portions of the 4
Information for which exemption is sought. However, the staff will withhold this letter from public a disclosure for 30 calendar dag frem the date of this letliftd'alloWWestinghouse the opportunity s,
fo verify the staffs conclusions, if, after that time, you do not request that all or portions of tho' Y
, information in the enclosures be withheld from public disclosure in accordance with 10 CFR sj 2.790, this letter will be placed in the NRC's Public Document Room.
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-if you have any questions regarding this matter, you can contact me si g3v1) 4151120,
Sincere!y, 0
original signed by:
Thomas J. Kenyon, Project Manager Standarlization Project Directorate
,O Division of Reactor Program Management 1
Office of Nuclear Reactor Regulation G
Docket No. 52 003
Enclosure:
As stated kh M g g tg,py cc w/ encl: See next page DISTRIBUTION: Enclosure to be held for 30 days g0)
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d To receive a copy of *f2 hicent, Indicate in the box: "C" = Copy without b< attachment /enclosura s *E" = Co )y, t.h attachment / enclosure
- N" = No copy i
I OFFICE PM:PhDPRM DiF DST:DRPM NAME DDCTsg "40M DATE 12/'N97
^ l 12/N97Nb s
Mr. Nicholas J Uperulo Docket No.52-003 Westinghouse Electric Corporation AP600 cc:
Mr. B. A. McIntyre Ms. Cindy L Haag Advanced Plant Safety & Ucensing Advanced Plant Safety & Ucensing Westinghcuse Electric Corporation Westinghouse Electric Corporation Energy Systems Business Unit Energy Systems Business Unit P.O. Box 355 Box 355 Pittsburgh, PA 15230 Pittsburgh, PA 15230 Enclosure to be distributed to the following addressees a:ter the result of the proprietary evaluation is f
received from Westinghouse:
Mr. Russ Bell Ms. Lynn Connor Senior Project Manager, Programs DOC-Search Associates Nuclear Energy Institute Post Office Box 34 1776 i Street, NW Cabin John, MD 20818 Suite 300 Washington, DC 20006 3706 M'
obert H. Buchholz Ge Nuclear Energy Dr. Craig D. Sawyer, Manager 175 Curtner Avenue, MC 781 Advanced Roscior Programs San Jose, CA 95125 GE Nuclear Energy 175 Curtner Avenue, MC 754 Mr. Storting Franks San Jose. CA 95125 U.S. Department of Energy NE 50 Berton Z. Cowan. Esq.
19901 Germantown Road Eckert Seamans Cherin & Mellott Germantown, MD 20874 600 Grant Street 42nd Floor Pittsburgh, PA 1521g Mr. Charles Thompson, Nuclear Engineer APG00 Certification Mr. Frank A. Ross NE 50 U.S. Department of Energy, NE-42 19901 Germantown Road Office of LWR Safety and Technology Germantown, MD 20874 19901 Germantown Road Germantown, MD 20874 Mr. Ed Rodwell, Manager PWR Design Certification Electric Power Research institute 3412 Hillview Avenue Palo Alto, CA 94303
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4 OPEN ITEM ON SSAR SECTION S.4 l
470.4SF GDC 19 requires that the control room be designed to provide adequate radiation protection F.t^::..g personnel to access and occupy the control room under sooident conditions. Westinghouse has proposed that this requirement be met by
- i incorpcrating sufflaient shield walls and by the installation of redundant non-ni:Fi".ed supplemental air filtration units (VBS) and a safety-related l
emergency bottled air pressurtsstion system (VES). Westinghouse submitted a radiological consequence analysis for personnel in the main control room (MCR) during a design basis loss-of coolant accident (LOCA) in SSAR Section 15.1.5.4.
l The staff has reviewed Westinghouse's justifloation for deviating from the occupancy factors referenood in Section 6.4 of the Standard Review Plan (SRP),
j and has determined that there is nothing unique about the APS00 MCR de61gn to justify using less conservative occupancy factors for personnel in the main control room Therefore, the st.ff concludes that the occupancy fectors used by 1
Westinghouse are unacceptable, and that the applicant should use the occupancy -
j factors referonood in Section 6.4 of the SRP.
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The staff has performed an independent radiological consequence calculation for -
the MCR emergency ventilation system (VES) under *high high" radiation level as described in the AP600 SSAR Section 6.4. The staff used the following.
parameters in hs analysis: the NUREG 1435 source term, NRC aerosol removal i
rates inside the containment, the control room X/Q values and inleskage rates provided by Westinghouse, and the control room occupancy factors referenced in.
Section 6.4 of the SRP. Table i provides the assumptions and estimates of the radiological consequences to the control room operators following a LOCA.
Sased on its calculations, the staff concludes that the VES under "high high" radiation conditions as described in the AP600 SSAR Section 6.4 is not capable i
of m!tigating the dose in the main control room following a design-basis LOCA to meet the dose criteria specified in GDC 19 of Appendix A to 10 CFR Part 50 (as applied to the AP600 design: 5 rom TEDE). This it sue should be resolved in conjunction with Q470.41F 470.44F.
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Table 1. Assumptions and Estimates of the Rdological Consequences to Control Room operators Following a LOCA for the AP600 Control room free volume 3.57E+4 ft' Time of bottled air depleted 72 hr l
Prior to depletion of bottled air Flow from compressed air bottles 23 ft' Unfmered inloakage 0 to 12 hr 2.5 cfm 12 to 72 hr 5.0 cfm t
After depletion of bottled av Air intake flow 1700cfm Filter efficiencies N/A Recirculation fl0w N/A Breathing rate of operators in control roem for the course of the accident 3.47E 4 m'/sec Atmospheric dispersion values 0 to 2 hr 1.8E 3 sec/m' 2 to 8 hr 1.3E 3 sec/m' 8 to 24 hr 1.1E 3 sec/m' 24 to 72 hr 7.3E-4 sec/m' 72 to 96 hr 8.4E-4 sec/m' 96 to 720 hr 4.8E-4 socim' Control room operator occupational factors 0 to 24 hr 1
24 to 96 hr 0.6 96 to 720 hr 0.4 4
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